Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review

Abdellatif, Hossam H.; Bhowmik, Palash K.; Arcilesi, David; Sabharwall, Piyush

doi:10.1016/j.pnucene.2023.105021

Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review

Journal Article · Fri Dec 22 23:00:00 EST 2023 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2023.105021· OSTI ID:2293507

Abdellatif, Hossam H. ^[1]; ^[2]; Arcilesi, David ^[1]; Sabharwall, Piyush ^[2]

University of Idaho, Idaho Falls, ID (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

According to historical records of reactor-related incidents, a steam generator tube rupture (SGTR) is one of the most common occurrences at operating pressurized water reactors (PWRs). Such design-basis accidents (DBAs) could lead to a direct path for radionuclides to be released to the atmosphere via the safety and relief valves, making assessments of radionuclide discharge from operating nuclear power plants (NPPs) into the environment crucial for ensuring safety. In such analyses, the primary focus has been on the extent of radioactive release, not the potential damage to the core. Moreover, significant and timely intervention by operators is needed during the initial stages of SGTRs in order to avert overfilling of the SGs, as well as to restrict the dissemination of radioactive materials. Determining the event sequence and phases that occur during an SGTR incident in an advanced passive (e.g., AP1000) water-cooled nuclear reactor is crucial for implementing effective passive safety systems (PSSs) for a specific water-cooled small modular reactor (SMR) design. Here this study provides a comprehensive review of the accident event progression, associated physical phenomena, knowledge gaps, and key performance indicators that must be evaluated and assessed in thermal-hydraulics models, based on relevant test data, respectively.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Accelerator R&D and Production (ARDAP)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2293507

Alternate ID(s):: OSTI ID: 2565804
OSTI ID: 2263254

Report Number(s):: INL/JOU--23-73449-Revision-0

Journal Information:: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 168; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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